Micro-reactor core mechanical support

ABSTRACT

A nuclear reactor core mechanical support bracket is disclosed. The support bracket includes a housing, a spring disposed internally within the housing, a shaft slidingly disposed within the housing, a shaft travel pin, and a flange. The shaft is configured to engage the spring to compress and decompress the spring as the shaft travels in and out of the housing. The shaft travel pin controls the travel of the shaft. The flange is configured to mount the nuclear reactor core mechanical support bracket to a canister of a nuclear reactor. The shaft includes an inset configured to interface with a nuclear reactor core component.

CROSS-REFERENCE TO RELATED APPLICATIONS

This application is a divisional application claiming priority under 35U.S.C. § 120 to U.S. patent application Ser. No. 17/156,977, entitledNUCLEAR REACTOR CORE SUPPORT SYSTEM PROVIDING RADIAL AND AXIAL SUPPORT,filed Jan. 25, 2021, the entire disclosure of which is herebyincorporated by reference herein.

STATEMENT REGARDING FEDERALLY SPONSORED RESEARCH OR DEVELOPMENT

This disclosure was made with government support under ContractDE-NE0008853 awarded by the Department of Energy. The government hascertain rights in this disclosure.

FIELD

The present disclosure is generally related to nuclear power generationand, more particularly, is directed to an improved device configured tomechanically support a core of a nuclear reactor.

SUMMARY

The following summary is provided to facilitate an understanding of someof the innovative features unique to the aspects disclosed herein, andis not intended to be a full description. A full appreciation of thevarious aspects of the present disclosure can be gained by taking theentire specification, claims, and abstract as a whole.

In one aspect, the present disclosure provides a nuclear reactor coremechanical support bracket. The support bracket comprises a housing; aspring disposed internally within the housing; a shaft slidinglydisposed within the housing and to engage the spring to compress anddecompress the spring as the shaft travels in and out of the housing; ashaft travel pin to control the travel of the shaft; and a flange tomount the support bracket to a canister of a nuclear reactor. The shaftfurther comprises an inset configured to interface with a nuclearreactor core component.

In another aspect, the present disclosure provides a nuclear reactor.The nuclear reactor comprises a reactor core; a canister to contain andseal the reactor core within the canister; and a core mechanical supportsystem configured to mount to the canister. The core mechanical supportsystem comprises: a radial core mechanical support system to support thereactor core in a radial direction; and an axial core mechanical supportsystem to support the reactor core in an axial direction.

In yet another aspect, the present disclosure provides a nuclearreactor. The nuclear reactor comprises: a reactor core; a canister tocontain and seal the reactor core within the canister; and a coremechanical support system configured to mount to the canister; a radialreflector disposed within the canister; a support beam disposed betweenan inner wall of the canister and the radial reflector; a plate disposedon each end of the reactor core, wherein the axial core mechanicalsupport system is configured to interface with the plate. The radialsupport bracket and the axial support bracket each comprises: a housing;a spring disposed internally within the housing; a shaft slidinglydisposed within the housing and to engage the spring to compress anddecompress the spring as the shaft travels in and out of the housing,the shaft further comprising an inset configured to interface with thesupport beam or the plate; a shaft travel pin to control the travel ofthe shaft; and a flange to mount the support bracket to the canister.The core mechanical support system comprises: a radial core mechanicalsupport system to support the reactor core in a radial direction; and anaxial core mechanical support system to support the reactor core in anaxial direction. The support beam is disposed axially along the lengthof the reactor core. The radial core mechanical support system comprisesa radial support bracket configured to interface with the support beam.

Further, it is understood that any one or more of thefollowing-described forms, expressions of forms, examples, can becombined with any one or more of the other following-described forms,expressions of forms, and examples.

The foregoing summary is illustrative only and is not intended to be inany way limiting. In addition to the illustrative aspects, embodiments,and features described above, further aspects, embodiments, and featureswill become apparent by reference to the drawings and the followingdetailed description.

BRIEF DESCRIPTION OF THE DRAWINGS

Various features of the aspects described herein are set forth withparticularity in the appended claims. The various aspects, however, bothas to organization and methods of operation, together with advantagesthereof, may be understood in accordance with the following descriptiontaken in conjunction with the accompanying drawings as follows:

FIG. 1 is a perspective view of a nuclear reactor comprising a coremechanical support system, in accordance with at least one non-limitingaspect of the present disclosure.

FIG. 2 is a longitudinal sectional view of the nuclear reactor shown inFIG. 1 , in accordance with at least one non-limiting aspect of thepresent disclosure.

FIG. 3 is a cross sectional view of the nuclear reactor shown in FIGS. 1and 2 , in accordance with at least one non-limiting aspect of thepresent disclosure.

FIG. 4 is a perspective longitudinal and cross sectional view of thenuclear reactor shown in FIGS. 1-3 , in accordance with at least onenon-limiting aspect of the present disclosure.

FIG. 5 is a perspective view of a radial and axial support bracket, inaccordance with at least one non-limiting aspect of the presentdisclosure.

FIG. 6 is a perspective view of Belleville washer springs, in accordancewith at least one non-limiting aspect of the present disclosure.

FIG. 7 is a perspective longitudinal sectional view of the nuclearreactor core shown in FIGS. 1-4 , in accordance with at least onenon-limiting aspect of the present disclosure.

Corresponding reference characters indicate corresponding partsthroughout the several views. The examples set out herein illustratevarious aspects of the claimed subject matter, in one form, and suchexamples are not to be construed as limiting the scope of the claimedsubject matter in any manner.

DETAILED DESCRIPTION

Applicant of the present application owns the following U.S. Provisionalpatent applications, filed on the same date, the disclosure of each ofwhich is herein incorporated by reference in its respective entirety:

-   -   U.S. patent application Ser. No. 17/080,241, titled ENHANCED        GRAPHITE NEUTRON REFLECTOR WITH BERYLLIUM OXIDE INCLUSIONS,        filed Oct. 26, 2020;    -   U.S. patent application Ser. No. 17/084,365, titled DEVICES,        SYSTEMS, AND METHODS FOR ADJUSTING THE OUTPUT OF A REACTOR CORE,        filed Oct. 29, 2020; and    -   U.S. patent application Ser. No. 17/084,403, titled DEVICES,        SYSTEMS, AND METHODS FOR CONFIGURING THE LAYOUT OF UNIT CELL OF        A REACTOR CORE, filed Oct. 29, 2020.

Before explaining various aspects of a nuclear reactor comprising a coremechanical support system, it should be noted that the illustrativeexamples are not limited in application or use to the details ofconstruction and arrangement of parts illustrated in the accompanyingdrawings and description. The illustrative examples may be implementedor incorporated in other aspects, variations, and modifications, and maybe practiced or carried out in various ways. Further, unless otherwiseindicated, the terms and expressions employed herein have been chosenfor the purpose of describing the illustrative examples for theconvenience of the reader and are not for the purpose of limitationthereof. Also, it will be appreciated that one or more of thefollowing-described aspects, expressions of aspects, and/or examples,can be combined with any one or more of the other following-describedaspects, expressions of aspects, and/or examples, without limitation.

In various aspects, the present disclosure is directed to a nuclearreactor comprising a core mechanical support system to support thereactor core and maintain the reactor core in a predetermined position.In one aspect, the nuclear reactor is a solid state micro-reactorcomprising an active core, a reflector, and the core mechanical supportsystem. The reactor core provides nuclear, thermal, and mechanicalinterfaces to fuel, heat removal systems, shutdown systems, reactivitycontrol systems, and instrumentation, for example, among others. Thereactor core is located inside a pressure tight canister. The coremechanical support system is configured to mechanically support andmaintain the reactor core, and corresponding components, in apredetermined position and configuration during all anticipated eventsincluding shipping and handling, operation, accident, and beyond designaccident conditions, without limitation. In an effort to avoid overconstraint and overstress of the reactor core components, thethermo-mechanical design of the core mechanical support system mayaccommodate various static and dynamic loading, differential thermalexpansion and changes in core component geometry during irradiation(swelling, shrinking, etc.).

Turning now to the figures, FIG. 1 is a perspective view of a nuclearreactor 10 comprising a core mechanical support system, in accordancewith at least one non-limiting aspect of the present disclosure. In oneaspect, the nuclear reactor 10 is a solid state micro-reactor. Thenuclear reactor 10 comprises a core 100 (FIGS. 2-4 and 7 ), a reflector106 (FIGS. 2-4 and 7 ), and a core mechanical support system containedwithin a pressurized canister 120. Front and rear canister closurebulkheads 122, 124 mechanically seal the core 100, reflector 106, andother components inside the canister 120.

FIG. 2 is a longitudinal sectional view of the nuclear reactor 10 shownin FIG. 1 , in accordance with at least one non-limiting aspect of thepresent disclosure. With reference to FIGS. 1 and 2 , the reactor core100 is contained within the canister 120. The core 100 comprises aplurality of reactivity control cells 104 configured to accommodate aplurality of reactivity control rods 115. Shut down rods cancollectively work to control the fission occurring within the core 100and therefore, prevent the core 100 from achieving a criticaltemperature in the event of a reactor 10 power failure and/orcriticality accident. According to various non-limiting aspects, theamount of fission can be reduced or completely eliminated within thecore 100, the latter of which can shut down the core 100. The reactivitycontrol rods 115 contemplated by the present disclosure can include aneutron absorbing material and be configured to be inserted into thereactivity control cells 104 to slow and/or stop the nuclear reactionsin the case of an emergency. The reactivity control configuration of thecore 100 represents a feature of modern micro-reactors, which aretransportable and have a broader range of commercial applications.Accordingly, the emergence of micro-reactors can increase the prevalenceof nuclear technology and the risk of any significant adverse eventsfrom the increase can be minimized.

The core 100 comprises a graphite core block 130 and a radial reflector106 that surrounds the graphite core block 130, among other componentsdescribed herein. According to the non-limiting aspect of FIG. 2 , thereflector 106 can include stationary and movable parts. The movableparts could be a control drum including a reflector material (e.g.,Beryllium Oxide [BeO]) and a sector of absorber material (e.g., BoronCarbide [B4C]). The drum acts as a reflector or as an absorber dependingon its rotation relative to the graphite core block. In one aspect, thereflector 106 includes one or more plates composed of a thick, neutronmoderating material configured to substantially surround the graphitecore block 130. The core 100 provides nuclear, thermal, and mechanicalinterfaces to fuel, heat removal system, shutdown and reactivity controlsystems, instrumentation, etc. The core 100 is located inside thepressure tight canister 120 and is surrounded by the reflector 106. Thecore 100 and corresponding components are mechanically supported by themechanical support system during all anticipated conditions includingshipping and handling, operation, accident and beyond design accidentconditions.

A core mechanical support system comprising a radial support system 125and an axial support system 127 supports and maintains the core 100 in apredetermined position and configuration during a variety of anticipatedevents including shipping and handling, operation, accident, and beyonddesign accident conditions, without limitation. In an effort to avoidover constraint and overstress of the reactor core 100 and associatedcomponents, the thermo-mechanical design of the core mechanical supportsystem may accommodate various static and dynamic loading, differentialthermal expansion and changes in core component geometry duringirradiation (swelling, shrinking, etc.). The core support systemseparates (as practically as possible) support for axial and radialdirection of the cylindrical core 100 located horizontally. In thisaspect, the dimensional changes of the core 100 components in the radialdirection do not significantly affect the reaction forces in the axialdirection and vice versa.

The radial support system 125 comprises a number of radial supportbrackets 126 surrounding the core 100 and the axial support system 127comprises a number of axial support brackets 128 located at both ends ofthe core 100. The radial support brackets 126 and the axial supportbrackets 128 support and maintain the core 100 in a predetermined radialand axial position during shipping and handling, operation, accident andbeyond design accident conditions. The radial support brackets 126interface with support beams 132, which engage the radial reflector 106,to uniformly distribute the load of the core 100, as discussed in moredetail hereinbelow. The support beams 132 are disposed between an innerwall of the canister 120 and the reflector 106. The support beams 132are disposed axially along the length of the core 100. The axialsupports brackets 128 interface with plates 148 to uniformly distributethe load of the core 100, as discussed in more detail hereinbelow. Withreference now also to FIGS. 5 and 6 , each radial/axial support bracket126, 128 comprises at least one spring 134 that is compressed by a shaft136 that travels in and out of the radial/axial support bracket 126, 128housing 138. The radial/axial support bracket 126, 128 interface withthe support beams 132 and/or plates 148 at the connection inset 140 ofthe radial/axial support bracket 126, 128. In the illustrated aspect,each radial/axial support bracket 126, 128 comprises four springs 134and each spring 134 comprises a number of washers 146.

FIG. 3 is a cross sectional view of the nuclear reactor 10 shown inFIGS. 1 and 2 , in accordance with at least one non-limiting aspect ofthe present disclosure. FIG. 4 is a perspective longitudinal and crosssectional view of the nuclear reactor 10 shown in FIGS. 1-3 , inaccordance with at least one non-limiting aspect of the presentdisclosure. With reference now to FIGS. 1-4 , according to onenon-limiting aspect, the core 100 includes a plurality of unit cells102, which collectively form hexagonal core boundaries. Each unit cell102 can be configured to accommodate a heat pipe 113 and an amount offuel (e.g. in the form of a rod 111 and/or stack configuration), whichcan collectively generate nuclear power and manage thermal energythroughout the core 100. According to some non-limiting aspects, one ormore unit cells 102 can further include a moderator configuration, whichcan slow down neutrons emitted from the fuel. The unit cells 102 can bearranged such that the core 100 includes a hexagonal geometry. However,in other non-limiting aspects, the unit cells 102 can be arranged suchthat the core 100 may include any of a number of different geometricalconfigurations, depending on intended application and/or userpreference.

With reference to FIGS. 3 and 4 , the reflector 106 can further includea plurality of control drums 108 configured to house a neutronabsorptive and reflective materials. In the event of a reactor and/orpower failure, the control drums 108 can turn inward towards the core100 such that the absorptive material can shut down the reactor.According to some non-limiting aspects, the reflector 106 canadditionally include a gamma shield configured to provide gamma andneutron shielding. The reflector can be configured to substantiallysurround the neutron shield, the core 100, and its internal components102, 104, 111, 113, 115 to further mitigate radiation. As depicted inthe non-limiting aspect of FIGS. 3 and 4 , the reflector 106 can bearranged in a circular configuration that surrounds the hexagonallyarranged plurality of unit cells 102. However, in other non-limitingaspects, the reflector 106 can be arranged to form any of a number ofdifferent geometrical configurations about the plurality of unit cells102, depending on intended application and/or user preference.

Still referring to FIGS. 3 and 4 , the reflector 106 can be sectioned toensure that a gap exists between the unit cells 102 and the reflector106 as a means of controlling and promoting a desired amount of heattransfer. For example, the reflector 106 can be formed from a pluralityof modular plates integrated to create the aforementioned gap. In othernon-limiting aspects, however, the reflector 106 can be integrallyformed. Additionally, the reflector 106 can be further configured toextend along an axial direction, which defines a length of the core 100.The plurality of unit cells 102 can also be configured to span thelength of the core 100.

Some compact reactors function as a “nuclear battery” which uses energyfrom the fission of nuclear materials (e.g. uranium in an oxide,metallic and/or silicide form, amongst others) to generate electricity.Since the unit cells are configured to accommodate fuel, in any form,including such radioactive isotopes, the magnitude of the length L ofthe core 100 can correspond to a desired output of the nuclear reactorand the fuel mass necessary to maintain criticality. Additionally and/oralternatively, the increased versatility of micro-reactors mean the core100 must be configurable for a wide variety of applications, many ofwhich might have size and/or weight constraints. Therefore, the designof core 100 allows for the length L to be specifically configurable toaccommodate for the output, size, and/or weight requirements of thenuclear reactor.

Still with reference to FIGS. 3 and 4 , the plurality of unit cells 102and the plurality of reactivity control cells 104 can be particularlyarranged to establish the hexagonal configuration of the non-limitingaspect of the core 100. It is also evident that each unit cell 102 ofthe plurality of unit cells 102 and each reactivity control cell 104 ofthe plurality of reactivity control cells 104 include a hexagonalconfiguration as well. However, it shall be appreciated that thehexagonal configuration is exclusively depicted for illustrativepurposes. Accordingly, the present disclosure contemplates othernon-limiting aspects in which the unit cells 102 and reactivity controlcells 104 include any number of geometrical configurations (e.g. square,circular, triangular, rectangular, pentagonal, octagonal) and arrangedsuch that the core 100 can include any number of geometricalconfigurations.

In further reference of FIGS. 3 and 4 , the plurality of unit cells 102and the plurality of reactivity control cells 104 can be arranged alonga radial direction, thereby defining a radial dimension of the core 100.Specifically, the core 100 shown in FIGS. 3 and 4 comprises 48 unitcells 102 and 13 reactivity control cells 104. The present disclosure,however, contemplates other non-limiting aspects wherein the core 100may include any number of unit cells 102 and reactivity control cells104. It will be appreciated that the ability to easily add or subtractthe number of unit cells 102 or reactivity control cells 104 to the core100 without dramatically altering its design allows the core 100 to beeasily scaled depending on the intended application and/or userpreference. As such, the output of the core 100 design can also beeasily adjusted for a multitude of applications and requirements. Forexample, a user can change the radial and/or axial dimension of the core100 by adding or subtracting unit cells 102 or reactivity control cells104 to the core 100. Since the unit cells are configured to accommodatefuel including radioactive isotopes, increasing or decreasing themagnitude of the radial dimension can alter the output of the core 100.Accordingly, the radial dimension of the core 100 can correspond to adesired output of the nuclear reactor depending on the intendedapplication and/or user preference. Additionally and/or alternatively,the radial dimension of the core 100 can be specifically configured tocomply with a multitude of size and/or weight requirements, which canvary by application. Accordingly, the core mechanical support system canbe modified by adding or removing radial/axial support brackets 126, 128of the radial support system 125 and the axial support system 127 toaccommodate changes in the radial and/or axial dimensions of the core100.

It shall be appreciated that the term “radial”, as used in the presentdisclosure, describes any direction extending from the center of thecore 100 when viewed from the top. Accordingly, the use of the term“radial” shall not be limited to circular or circular-likeconfigurations and shall not be construed to imply that the core 100 ofFIGS. 1-4 is limited to circular, or circular-like, configurations. Forexample, the present disclosure contemplates non-limiting aspects inwhich the core 100 includes a rectangular cross-section configuration.According to such aspects, the core 100 can include one or more radialdimensions of varying lengths. With reference to FIGS. 2 and 4 , theplurality of unit cells 102 and the plurality of reactivity controlcells 104 can be integrally formed from a solid block 130 of material(e.g. graphite). Thus, the internal features of each of the unit cells102, such as heat pipe channels, fuel channels, moderator channels,and/or the like, can be bored out of—and integrally formed from—thesolid block of material. However, according to other non-limitingaspects, each unit cell 102 of the plurality of unit cells 102 and eachreactivity control cell 104 can be modularly formed and integrated intothe core block 130 to promote the adjustability of the core 100 design.

Regardless, the core 100 can be easily manufactured to include anynumber of unit cells 102 and/or reactivity control cells 104. This canallow the core 100 design to be easily scalable, an obvious improvementover known reactors. For example, altering the number of unit cells 102and reactivity control cells 104 allows the user to alter the radialdimension R and axial length L (FIG. 1 ) of the core 100, therebyaltering its output and flexibility for applications with unique outputand/or space constraints. The core 100 design, however, essentiallyremains the same, which allows for predictability in production andperformance regardless of the difference in output and size. Thesefeatures also reduce the amount of non-recurring engineering required todesign for a new application and facilitates manufacturing consistencyand the standardization of parts. Although the core 100 can be scaled asa means of adjusting its output, the scaling should further consider thepower rating of the implemented heat pipes, the appropriate number ofreactivity control rods required for the adjusted output, and theeffectiveness of the control drums.

According to other non-limiting aspects, the unit cell 102 can furtherinclude a moderator channel configured to accommodate a moderator (e.g.a hydride-based moderator, BeO, etc.) of the core 100, wherein themoderator can be configured to retard and the propagation of neutronsemitted by fuel inserted in the plurality of fuel channels 110.Alternatively and/or additionally, the unit cell 102 can includeadditional features, configured to accommodate other instrumentation ofthe core 100.

Still referring to FIGS. 3 and 4 , the unit cell 102 also can includefeatures configured to accommodate a neutron absorbing materials thatcan slow the nuclear reactions occurring in the fuel channels 110 of theunit cells 102. Accordingly, the power distribution and radial powerpeaking of the unit cells 102—and consequentially, the core 100itself—can be further adjusted via the influence of neutron absorbers.According to some non-limiting aspects, the core 100 can be designed foran application that does not impose a strict transportation requirementon the core 100. Alternatively and/or additionally, the core 100 can usea high-density fuel. According to such aspects, the axial power peakingfactor and axial power distribution of the unit cells 102 and core 100can be otherwise managed by varying the fuel enrichment level within thefuel channels 110 of the unit cells 102 or by adding burnable absorbers.

Similarly, the reflector 106 configuration may include a plurality ofreflectors 106 including control drums 108, wherein the reflectors 106are configured to extend along at least a portion of the length L of thecore 100. Of course, according to some non-limiting aspects, thereflectors too can be integrally formed. Again, the reflectors can bespecifically configured to create advantageous gaps to promote andenhance heat transfer throughout the core 100.

According to non-limiting aspects of FIGS. 1-4 , the core 100 can beassembled to include a fuel 111 (e.g. rods and/or stacks), heat pipes113, and reactivity control rods 115 dispositioned throughout theplurality of unit cells 102 and reactivity control cells 104.Specifically, the fuel 111 can be dispositioned throughout the fuelchannels 110 of one or more unit cells 102, the heat pipes 113 can bedispositioned throughout the heat pipe channels 112 (FIG. 3 ) of one ormore unit cells 102, and the reactivity control rods 115 can bedispositioned through a reactivity control channel (not shown) of one ormore reactivity control cells 104. According to some non-limitingaspects, the fuel 111 and heat pipes 113 are configured to extend thepredetermined length L of the core 100. In other non-limiting aspects,the fuel 111 and heat pipes 113 are configured to extend an additionallength beyond the predetermined length L of the core, to facilitatedownstream ex-core connections and/or equipment (e.g. power systems,condensers, structural supports). This design allows the core 100 to becustomized for any intended application and/or user preference, whichenables it to be versatile in response to customer needs. Thesealterations, however, can be evaluated using the underlying nuclearphysics and/or manufacturability of the core 100 design, which preservesreliability and predictability in core 100 production and operation. Inother words, the assembled core 100 allows the fuel 111 and heat pipes113 to be specifically configured to accommodate for any specific powerrequirement and/or structural configuration without having to reinventthe basic core 100 design and assume the inherent development risks.

Still referring to FIGS. 1-4 , the core 100 can further include aplurality of reactivity control rods 115 configured to be dispositionedthrough one or more reactivity control cell 104 of the plurality ofreactivity control cells 104. For example, the reactivity control cells104 can include a reactivity control rod or reactivity control channelsimilar to the fuel channels 110 and/or heat pipe channels 112, butspecifically configured to accommodate a reactivity control rod 115. Aspreviously discussed, each reactivity control rod 115 can include aneutron absorbing material configured to slow and/or stop the nuclearreactions within the core 100 in the case of an emergency. Thereactivity control rods 115 can collectively work to prevent the core100 from achieving a critical temperature or prompt criticality in theevent of a reactor and/or power failure. Accordingly, the emergence ofmicro-reactor can increase the prevalence of nuclear technology, makingsafety a higher priority.

FIG. 5 is a perspective view of a radial and axial support bracket 126,128, in accordance with at least one non-limiting aspect of the presentdisclosure. The main component of the core support system is aradial/axial support bracket 126, 128 comprising a preloaded springblock. Each spring block of the radial/axial support bracket 126, 128comprises various number of springs 134 as shown in more detail in FIG.6 . Each radial/axial support bracket 126, 128 comprises a number ofsprings 134 located internal to the bracket housing 138. Each spring 134is preloaded or compressed by a shaft 136 that is slidingly disposedwithin the bracket housing 138 and interfaces with a support beam 132(FIGS. 2-4 ) at the connection inset 140. The shaft 136 is configured toengage the spring 134 to compress and decompress the spring 134 as theshaft 136 travels in and out of the bracket housing 138. The travel ofeach bracket shaft 136 is controlled by a shaft travel pin 142, whichalso prevents rotation of the bracket shaft 136. The radial/axialsupport bracket 126, 128 can be mounted to the external canister 120(FIGS. 1, 2, 4 ) by the support bracket flange 144. A number of radialsupport brackets 126 are located around the core 100 (FIGS. 1-4 ) and anumber of axial support brackets 128 are located at either end of thecore 100 to create a desirable support for the core 100 in a radial andaxial direction. The reaction forces corresponding to the preloadedspring block radial/axial support bracket 126, 128 act against internalwalls of the pressure tight canister 120. In one aspect, the and thebracket body comprising the housing 138, bracket flange 144, shaft 136,and shaft travel pin 142 may be made of 304 stainless steel. Thematerials of construction can also be modified depending onenvironmental conditions.

FIG. 6 is a perspective view of Belleville washer springs 134, inaccordance with at least one non-limiting aspect of the presentdisclosure. In one aspect, the spring in the preloaded spring blockradial/axial support bracket 126, 128 may be a disc spring such as aBelleville washer spring 134, for example. The Belleville washer spring134 may be made of high-strength, corrosion-resistant age-hardenablealloy such as nickel chromium material that can be readily fabricatedinto complex parts. In one aspect, the Belleville washer spring 134 ismade of Alloy 718 material. With reference to FIGS. 5 and 6 , theradial/axial support bracket 126, 128 should not be limited in thedisclosed context as a variety of other configurations may be employed.Other aspects of the bracket housing 138 or body is configured to housethe Belleville washer springs 134 in a compressed state via the shaft136 with the shaft travel pin 142. The number of Belleville washersprings 134 and the number of Belleville washers 146 in the spring canvary. The Belleville washer 146 has frusto-conical shape that gives thewasher 146 its characteristic spring. The dimensions of any individualcomponent also can be varied. The materials of construction can also bemodified depending on environmental conditions. In various aspects, TheBelleville washer 146 is a type of spring shaped like a washer. TheBelleville washer spring 134 may be referred to as a coned-disc spring,conical spring washer, disc spring, Belleville spring, or cupped springwasher, comprise a conical shell which can be loaded along its axiseither statically or dynamically.

It will be appreciated that the number of radial/axial support brackets126, 128 and preloaded spring 134 characteristics may be selected toensure that the “as-built” preload force is in a range of forcescorresponding from 1 g to 10 g acceleration. In one aspect, thedeflection of the spring 134 pack is sufficient to compensate for adifferential expansion between components of the core 100, canister 120,and the radial/axial core the support systems 125, 127 taking intoaccount thermal expansion and irradiation induced geometry anddimensional changes.

FIG. 7 is a perspective longitudinal sectional view of the nuclearreactor core 100 shown in FIGS. 1-4 , in accordance with at least onenon-limiting aspect of the present disclosure. The reactor core 100comprises a core mechanical support system comprising radial/axial corethe support systems 125, 127 comprising radial/axial support brackets126, 128 acting in axial (L) and radial (R) directions as describedherein. In this configuration, the core 100 is assembled with graphitecore blocks 130, fuel rods (not shown), heat pipes (not shown) and astationary radial reflector 106 located inside the pressurized canister120. The radial core support system 125 comprising a series of preloadedspring radial support brackets 126 interface with the core componentsusing beams 132 to uniformly distribute the load radially. The axialcore support system 127 comprising a series of preloaded spring axialsupport brackets 128 interface with plates 148 to uniformly distributethe load axially. The axial support brackets 128 can engage with theplates 148 via the shaft 136 and/or the inset 140.

With reference now to FIGS. 5-7 , the radial core support system 125comprises a series of the preloaded spring radial support brackets 126which interface with the core 100 component using beams 132 to uniformlydistribute the load. The radial support brackets 126 are located alongthe core 100 and uniformly distributed over the canister 120 wall in theaxial and hoop direction. The radial support brackets 126 are attachedto the canister 120 wall at one side by the flange 144. The other sideof the radial support bracket 126 interfaces with the beam 132 locatedalong the axial (L) length of the core 100 inside the canister 120. Thebeam 132 slidingly interfaces to the core 100 to allow a differentialexpansion between the graphite core block 130 components, the canister120, and the radial support bracket 126 and spring 134 pack. The numberand characteristic of the spring 134 pack located in the housing 138 ofthe radial bracket 126 is selected based on required preload,anticipated external load, and combined dimensional changes due todifferential thermal expansion and irradiation induced effects in theradial direction.

Still with reference to FIGS. 5-7 , the axial support brackets 128 areattached to the canister bulkhead 122, 124 and provides force to thecore graphite block 130 over the plates 148. A sliding interface betweenthe axial support bracket 128 and the plates 148 allow for adifferential expansion between the core graphite block 130 and thecanister 120. The number and characteristic of the spring 134 packlocated in the housing 138 of the axial support bracket 128 is selectedbased on the required preload, anticipated external load and combineddimensional changes due to differential thermal expansion andirradiation induce effects in the axial direction.

Various aspects of the subject matter described herein are set out inthe following numbered examples:

Example 1: A nuclear reactor core mechanical support bracket,comprising: a housing; a spring disposed internally within the housing;a shaft slidingly disposed within the housing and to engage the springto compress and decompress the spring as the shaft travels in and out ofthe housing, the shaft further comprising an inset configured tointerface with a nuclear reactor core component; a shaft travel pin tocontrol the travel of the shaft; and a flange to mount the supportbracket to a canister of a nuclear reactor.

Example 2: The nuclear reactor core mechanical support bracket ofExample 1, wherein the inset is configured to connect to a support beamaxially disposed along the length a nuclear reactor core.

Example 3. The nuclear reactor core mechanical support bracket of anyone or more of Examples 1-2, wherein the inset is configured to connectto a plate disposed at either end of a nuclear reactor core.

Example 4. The nuclear reactor core mechanical support bracket of anyone or more of Examples 1-3, wherein the spring is a disc springcomprising a disc washer spring.

Example 5. The nuclear reactor core mechanical support bracket ofExample 4, comprising a plurality of disc springs, wherein each one ofthe plurality of disc springs comprises a plurality of stacked discwasher springs.

Example 6. The nuclear reactor core mechanical support bracket of anyone of Examples 1-5, wherein the housing is made of stainless steel.

Example 7. The nuclear reactor core mechanical support bracket of anyone or more of Examples 1-6, wherein the spring is made of Alloy 718.

Example 8. A nuclear reactor, comprising: a reactor core; a canister tocontain and seal the reactor core within the canister; and a coremechanical support system configured to mount to the canister, whereinthe core mechanical support system comprises: a radial core mechanicalsupport system to support the reactor core in a radial direction; and anaxial core mechanical support system to support the reactor core in anaxial direction.

Example 9. The nuclear reactor of Example 8, further comprising: aradial reflector disposed within the canister; and a support beamdisposed between an inner wall of the canister and the radial reflector,wherein the support beam is disposed axially along the length of thereactor core; wherein the radial core mechanical support systemcomprises a radial support bracket configured to interface with thesupport beam.

Example 10. The nuclear reactor of Example 9, wherein the radial supportbracket comprises: a housing; a spring disposed internally within thehousing; a shaft slidingly disposed within the housing and to engage thespring to compress and decompress the spring as the shaft travels in andout of the housing, the shaft further comprising an inset configured tointerface with the support beam; a shaft travel pin to control thetravel of the shaft; and a flange to mount the support bracket to thecanister.

Example 11. The nuclear reactor of any one or more of Examples 8-10,further comprising a plate disposed on each end of the reactor core,wherein the axial core mechanical support system is configured tointerface with the plate.

Example 12. The nuclear reactor of Example 11, wherein the axial coremechanical support system comprises: a housing; a spring disposedinternally within the housing; a shaft slidingly disposed within thehousing and to engage the spring to compress and decompress the springas the shaft travels in and out of the housing, the shaft furthercomprising a shaft configured to interface with the plate; a shafttravel pin to control the travel of the shaft; and a flange to mount thesupport bracket to the canister.

Example 13. The nuclear reactor of Example 12, wherein the shaftcomprises an inset configured to engages the plate.

Example 14. The nuclear reactor of any one or more of Examples 8-13,wherein the radial core mechanical support system and the axial coremechanical support system are configured to support the reactor core inan axial direction provide a preload force in a range of forcescorresponding from 1 g to 10 g acceleration.

Example 15. A nuclear reactor, comprising: a reactor core; a canister tocontain and seal the reactor core within the canister; and a coremechanical support system configured to mount to the canister, whereinthe core mechanical support system comprises: a radial core mechanicalsupport system to support the reactor core in a radial direction; and anaxial core mechanical support system to support the reactor core in anaxial direction; a radial reflector disposed within the canister; asupport beam disposed between an inner wall of the canister and theradial reflector, wherein the support beam is disposed axially along thelength of the reactor core, wherein the radial core mechanical supportsystem comprises a radial support bracket configured to interface withthe support beam; a plate disposed on each end of the reactor core,wherein the axial core mechanical support system is configured tointerface with the plate; wherein the radial support bracket and theaxial support bracket each comprises: a housing; a spring disposedinternally within the housing; a shaft slidingly disposed within thehousing and to engage the spring to compress and decompress the springas the shaft travels in and out of the housing, the shaft furthercomprising an inset configured to interface with the support beam or theplate; a shaft travel pin to control the travel of the shaft; and aflange to mount the support bracket to the canister.

Example 16. The nuclear reactor of Example 15, wherein the shaftcomprises an inset configured to engages the support beam or the plate.

Example 17. The nuclear reactor of any one or more of Examples 15-16,wherein the radial core mechanical support system and the axial coremechanical support system are configured to support the reactor core inan axial direction provide a preload force in a range of forcescorresponding from 1 g to 10 g acceleration.

Numerous specific details are set forth to provide a thoroughunderstanding of the overall structure, function, manufacture, and useof the aspects as described in the present disclosure and illustrated inthe accompanying drawings. Well-known operations, components, andelements have not been described in detail so as not to obscure theaspects described in the present disclosure. The reader will understandthat the aspects described and illustrated herein are non-limitingexamples, and thus it can be appreciated that the specific structuraland functional details disclosed herein may be representative andillustrative. Variations and changes thereto may be made withoutdeparting from the scope of the claims. Furthermore, it is to beunderstood that such terms as “forward”, “rearward”, “left”, “right”,“upwardly”, “downwardly”, and the like are words of convenience and arenot to be construed as limiting terms.

In the present disclosure, like reference characters designate like orcorresponding parts throughout the several views of the drawings.

All patents, patent applications, publications, or other disclosurematerial mentioned herein, are hereby incorporated by reference in theirentirety as if each individual reference was expressly incorporated byreference respectively. All references, and any material, or portionthereof, that are said to be incorporated by reference herein areincorporated herein only to the extent that the incorporated materialdoes not conflict with existing definitions, statements, or otherdisclosure material set forth in this disclosure. As such, and to theextent necessary, the disclosure as set forth herein supersedes anyconflicting material incorporated herein by reference and the disclosureexpressly set forth in the present application controls.

The present disclosure has been described with reference to variousexamples and illustrative aspects. The aspects described herein areunderstood as providing illustrative features of varying detail ofvarious aspects of the disclosed invention; and therefore, unlessotherwise specified, it is to be understood that, to the extentpossible, one or more features, elements, components, constituents,ingredients, structures, modules, and/or aspects of the disclosedaspects may be combined, separated, interchanged, and/or rearranged withor relative to one or more other features, elements, components,constituents, ingredients, structures, modules, and/or aspects of thedisclosed aspects without departing from the scope of the disclosedinvention. Accordingly, it will be recognized by persons having ordinaryskill in the art that various substitutions, modifications orcombinations of any of the example aspects may be made without departingfrom the scope of the invention. In addition, persons skilled in the artwill recognize, or be able to ascertain using no more than routineexperimentation, many equivalents to the various aspects of theinvention described herein upon review of the present disclosure. Thus,the present disclosure is not limited by the description of the variousaspects, but rather by the claims.

Those skilled in the art will recognize that, in general, terms usedherein, and especially in the appended claims (e.g., bodies of theappended claims) are generally intended as “open” terms (e.g., the term“including” should be interpreted as “including but not limited to,” theterm “having” should be interpreted as “having at least,” the term“includes” should be interpreted as “includes but is not limited to,”etc.). It will be further understood by those within the art that if aspecific number of an introduced claim recitation is intended, such anintent will be explicitly recited in the claim, and in the absence ofsuch recitation no such intent is present. For example, as an aid tounderstanding, the following appended claims may contain usage of theintroductory phrases “at least one” and “one or more” to introduce claimrecitations. However, the use of such phrases should not be construed toimply that the introduction of a claim recitation by the indefinitearticles “a” or “an” limits any particular claim containing suchintroduced claim recitation to claims containing only one suchrecitation, even when the same claim includes the introductory phrases“one or more” or “at least one” and indefinite articles such as “a” or“an” (e.g., “a” and/or “an” should typically be interpreted to mean “atleast one” or “one or more”); the same holds true for the use ofdefinite articles used to introduce claim recitations.

In addition, even if a specific number of an introduced claim recitationis explicitly recited, those skilled in the art will recognize that suchrecitation should typically be interpreted to mean at least the recitednumber (e.g., the bare recitation of “two recitations,” without othermodifiers, typically means at least two recitations, or two or morerecitations). Furthermore, in those instances where a conventionanalogous to “at least one of A, B, and C, etc.” is used, in generalsuch a construction is intended in the sense one having skill in the artwould understand the convention (e.g., “a system having at least one ofA, B, and C” would include but not be limited to systems that have Aalone, B alone, C alone, A and B together, A and C together, B and Ctogether, and/or A, B, and C together, etc.). In those instances where aconvention analogous to “at least one of A, B, or C, etc.” is used, ingeneral such a construction is intended in the sense one having skill inthe art would understand the convention (e.g., “a system having at leastone of A, B, or C” would include but not be limited to systems that haveA alone, B alone, C alone, A and B together, A and C together, B and Ctogether, and/or A, B, and C together, etc.). It will be furtherunderstood by those within the art that typically a disjunctive wordand/or phrase presenting two or more alternative terms, whether in thedescription, claims, or drawings, should be understood to contemplatethe possibilities of including one of the terms, either of the terms, orboth terms unless context dictates otherwise. For example, the phrase “Aor B” will be typically understood to include the possibilities of “A”or “B” or “A and B.”

With respect to the appended claims, those skilled in the art willappreciate that recited operations therein may generally be performed inany order. Also, although claim recitations are presented in asequence(s), it should be understood that the various operations may beperformed in other orders than those which are described, or may beperformed concurrently. Examples of such alternate orderings may includeoverlapping, interleaved, interrupted, reordered, incremental,preparatory, supplemental, simultaneous, reverse, or other variantorderings, unless context dictates otherwise. Furthermore, terms like“responsive to,” “related to,” or other past-tense adjectives aregenerally not intended to exclude such variants, unless context dictatesotherwise.

It is worthy to note that any reference to “one aspect,” “an aspect,”“an exemplification,” “one exemplification,” and the like means that aparticular feature, structure, or characteristic described in connectionwith the aspect is included in at least one aspect. Thus, appearances ofthe phrases “in one aspect,” “in an aspect,” “in an exemplification,”and “in one exemplification” in various places throughout the presentdisclosure are not necessarily all referring to the same aspect.Furthermore, the particular features, structures or characteristics maybe combined in any suitable manner in one or more aspects.

As used herein, the singular form of “a”, “an”, and “the” include theplural references unless the context clearly dictates otherwise.

Directional phrases used herein, such as, for example and withoutlimitation, top, bottom, left, right, lower, upper, front, back, andvariations thereof, shall relate to the orientation of the elementsshown in the accompanying drawing and are not limiting upon the claimsunless otherwise expressly stated.

The terms “about” or “approximately” as used in the present disclosure,unless otherwise specified, means an acceptable error for a particularvalue as determined by one of ordinary skill in the art, which dependsin part on how the value is measured or determined. In certain aspects,the term “about” or “approximately” means within 1, 2, 3, or 4 standarddeviations. In certain aspects, the term “about” or “approximately”means within 50%, 200%, 105%, 100%, 9%, 8%, 7%, 6%, 5%, 4%, 3%, 2%, 1%,0.5%, or 0.05% of a given value or range.

In the present disclosure, unless otherwise indicated, all numericalparameters are to be understood as being prefaced and modified in allinstances by the term “about,” in which the numerical parameters possessthe inherent variability characteristic of the underlying measurementtechniques used to determine the numerical value of the parameter. Atthe very least, and not as an attempt to limit the application of thedoctrine of equivalents to the scope of the claims, each numericalparameter described herein should at least be construed in light of thenumber of reported significant digits and by applying ordinary roundingtechniques.

Any numerical range recited herein includes all sub-ranges subsumedwithin the recited range. For example, a range of “1 to 100” includesall sub-ranges between (and including) the recited minimum value of 1and the recited maximum value of 100, that is, having a minimum valueequal to or greater than 1 and a maximum value equal to or less than100. Also, all ranges recited herein are inclusive of the end points ofthe recited ranges. For example, a range of “1 to 100” includes the endpoints 1 and 100. Any maximum numerical limitation recited in thepresent disclosure is intended to include all lower numericallimitations subsumed therein, and any minimum numerical limitationrecited in the present disclosure is intended to include all highernumerical limitations subsumed therein. Accordingly, Applicant reservesthe right to amend the present disclosure, including the claims, toexpressly recite any sub-range subsumed within the ranges expresslyrecited. All such ranges are inherently described in the presentdisclosure.

Any patent application, patent, non-patent publication, or otherdisclosure material referred to in the present disclosure and/or listedin any Application Data Sheet is incorporated by reference herein, tothe extent that the incorporated materials is not inconsistent herewith.As such, and to the extent necessary, the disclosure as explicitly setforth herein supersedes any conflicting material incorporated herein byreference. Any material, or portion thereof, that is said to beincorporated by reference herein, but which conflicts with existingdefinitions, statements, or other disclosure material set forth hereinwill only be incorporated to the extent that no conflict arises betweenthat incorporated material and the existing disclosure material.

The terms “comprise” (and any form of comprise, such as “comprises” and“comprising”), “have” (and any form of have, such as “has” and“having”), “include” (and any form of include, such as “includes” and“including”) and “contain” (and any form of contain, such as “contains”and “containing”) are open-ended linking verbs. As a result, a systemthat “comprises,” “has,” “includes” or “contains” one or more elementspossesses those one or more elements, but is not limited to possessingonly those one or more elements. Likewise, an element of a system,device, or apparatus that “comprises,” “has,” “includes” or “contains”one or more features possesses those one or more features, but is notlimited to possessing only those one or more features.

In summary, numerous benefits have been described which result fromemploying the concepts described herein. The foregoing description ofthe one or more forms has been presented for purposes of illustrationand description. It is not intended to be exhaustive or limiting to theprecise form disclosed. Modifications or variations are possible inlight of the above teachings. The one or more forms were chosen anddescribed in order to illustrate principles and practical application tothereby enable one of ordinary skill in the art to utilize the variousforms and with various modifications as are suited to the particular usecontemplated. It is intended that the claims submitted herewith definethe overall scope.

The invention claimed is:
 1. A nuclear reactor core mechanical support bracket, comprising: a housing; a spring disposed internally within the housing; a shaft slidingly disposed at least partially within the housing and to engage the spring to compress and decompress the spring as at least a portion of the shaft travels in and out of the housing, the shaft further comprising an inset configured to interface with a nuclear reactor core component; a shaft travel pin to control the travel of the shaft; and a flange to mount the nuclear reactor core mechanical support bracket to a canister of a nuclear reactor.
 2. The nuclear reactor core mechanical support bracket of claim 1, wherein the inset is configured to connect to a support beam extending axially along a length of a core of the nuclear reactor.
 3. The nuclear reactor core mechanical support bracket of claim 1, wherein the inset is configured to connect to a plate disposed at either end of a core of the nuclear reactor.
 4. The nuclear reactor core mechanical support bracket of claim 1, wherein the spring is a disc spring comprising a disc washer spring.
 5. The nuclear reactor core mechanical support bracket of claim 4, comprising a plurality of disc springs, wherein each of the plurality of disc springs comprises a plurality of stacked disc washer springs.
 6. The nuclear reactor core mechanical support bracket of claim 1, wherein the housing is made of stainless steel.
 7. The nuclear reactor core mechanical support bracket of claim 1, wherein the spring is made of Alloy
 718. 8. A nuclear reactor core mechanical support bracket, comprising: a housing; springs disposed internally within the housing; shafts slidingly disposed at least partially within the housing, wherein each of the shafts corresponds to a different one of the springs, wherein each of the shafts compresses and decompresses the corresponding one of the springs as at least a portion of the respective shaft travels in and out of the housing, and wherein each one of the shafts further comprises an inset configured to interface with a nuclear reactor core component; shaft travel pins to control the travel of the shafts and prevent rotation of the shafts, wherein each of the shaft travel pins corresponds to a different one of the shafts; and a flange to mount the nuclear reactor core mechanical support bracket to a canister of a nuclear reactor.
 9. The nuclear reactor core mechanical support bracket of claim 8, wherein the inset of each of the shafts is configured to connect to a support beam extending axially along a length of a core of the nuclear reactor.
 10. The nuclear reactor core mechanical support bracket of claim 8, wherein the inset of each of the shafts is configured to connect to a plate disposed at either end of a core of the nuclear reactor.
 11. The nuclear reactor core mechanical support bracket of claim 8, wherein each the springs is a disc spring comprising a disc washer spring.
 12. The nuclear reactor core mechanical support bracket of claim 11, wherein the disc spring of each of the springs comprises a plurality of stacked disc washer springs.
 13. The nuclear reactor core mechanical support bracket of claim 8, wherein the housing is made of stainless steel.
 14. The nuclear reactor core mechanical support bracket of claim 8, wherein each of the springs is made of Alloy
 718. 15. The nuclear reactor core mechanical support bracket of claim 8, wherein the shafts comprise four shafts, and wherein the springs comprise four springs. 